CA3145777A1 - System for confining and cooling melt from the core of a nuclear reactor - Google Patents
System for confining and cooling melt from the core of a nuclear reactor Download PDFInfo
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- CA3145777A1 CA3145777A1 CA3145777A CA3145777A CA3145777A1 CA 3145777 A1 CA3145777 A1 CA 3145777A1 CA 3145777 A CA3145777 A CA 3145777A CA 3145777 A CA3145777 A CA 3145777A CA 3145777 A1 CA3145777 A1 CA 3145777A1
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- thermal shield
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- 238000001816 cooling Methods 0.000 title claims abstract description 24
- 239000000945 filler Substances 0.000 claims abstract description 48
- 230000004224 protection Effects 0.000 claims description 57
- 230000002093 peripheral effect Effects 0.000 claims description 35
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 28
- 230000000717 retained effect Effects 0.000 claims description 12
- 230000002787 reinforcement Effects 0.000 claims description 9
- 230000000284 resting effect Effects 0.000 claims description 6
- 239000002893 slag Substances 0.000 claims description 4
- 230000006378 damage Effects 0.000 abstract description 35
- 239000000155 melt Substances 0.000 abstract description 28
- 238000000034 method Methods 0.000 description 16
- 230000008569 process Effects 0.000 description 16
- 230000003993 interaction Effects 0.000 description 15
- 230000005855 radiation Effects 0.000 description 13
- 239000012634 fragment Substances 0.000 description 12
- 238000002844 melting Methods 0.000 description 12
- 230000008018 melting Effects 0.000 description 12
- 230000002028 premature Effects 0.000 description 10
- 230000015572 biosynthetic process Effects 0.000 description 9
- 230000004888 barrier function Effects 0.000 description 8
- 230000009471 action Effects 0.000 description 7
- 230000001846 repelling effect Effects 0.000 description 7
- 230000002441 reversible effect Effects 0.000 description 7
- 238000000926 separation method Methods 0.000 description 7
- 239000000126 substance Substances 0.000 description 7
- 238000010438 heat treatment Methods 0.000 description 6
- 239000002184 metal Substances 0.000 description 6
- 239000000443 aerosol Substances 0.000 description 5
- 230000008859 change Effects 0.000 description 4
- 238000004880 explosion Methods 0.000 description 3
- 238000009413 insulation Methods 0.000 description 3
- 239000007788 liquid Substances 0.000 description 3
- 102200052313 rs9282831 Human genes 0.000 description 3
- 238000006073 displacement reaction Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 230000004907 flux Effects 0.000 description 2
- 238000009434 installation Methods 0.000 description 2
- 230000036961 partial effect Effects 0.000 description 2
- 230000009993 protective function Effects 0.000 description 2
- 230000002829 reductive effect Effects 0.000 description 2
- 229910000831 Steel Inorganic materials 0.000 description 1
- 206010003549 asthenia Diseases 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 239000000110 cooling liquid Substances 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 238000002425 crystallisation Methods 0.000 description 1
- 230000008025 crystallization Effects 0.000 description 1
- 230000009977 dual effect Effects 0.000 description 1
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- 230000002706 hydrostatic effect Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000010309 melting process Methods 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 230000035485 pulse pressure Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/016—Core catchers
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/024—Supporting constructions for pressure vessels or containment vessels
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/10—Means for preventing contamination in the event of leakage, e.g. double wall
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention relates to the field of nuclear power engineering, and more particularly to systems which provide for the safety of nuclear power plants, and can be used in the event of serious accidents leading to the destruction of the pressure vessel and sealed containment structure of a reactor. The technical result of the claimed invention is an increase in the reliability of a system for confining and cooling melt from the core of a nuclear reactor, and an increase in the efficiency of heat removal from the melt from the core of a nuclear reactor. The technical result is achieved in that a system for confining and cooling melt from the core of a nuclear reactor includes a top thermal shield mounted in the zone between a housing and a cantilever truss, and a bottom thermal shield mounted inside the housing on an upper filler cassette.
Description
SYSTEM FOR CONFINING AND COOLING MELT FROM
THE CORE OF A NUCLEAR REACTOR
Pertinent art The invention relates to the field of nuclear power engineering, and more particularly to systems, which provide for the safety of nuclear power plants (NPP), and can be used in the event of serious accidents leading to the destruction of the pressure vessel and sealed containment structure of the reactor.
The accidents with core meltdown, which may take place during multiple io failure of the core cooling system, constitute the greatest radiation hazard.
During such accidents the core melt ¨ corium ¨ by melting the core structures and reactor pressure vessel escapes outside, and the afterheat retained in it may disturb the integrity of the NPP containment ¨ the last barrier in the escape routes of radioactive products to the environment.
is To exclude this, it is required to confine the core melt (corium) escaping from the reactor pressure vessel and provide its continuous cooling up to its complete crystallization. The system for confining and cooling melt from the core of a nuclear reactor performs this function, which prevents the damage of the NPP
containment and thereby protects the public and environment against exposure effect during 20 severe accidents of the nuclear reactors.
Prior art The system for confining and cooling melt from the core [1] of a nuclear reactor, which contains a guide plate installed under the reactor pressure vessel and resting on the cantilever truss installed in the embedded parts in the foundation of the 25 concrete pit of the layered vessel, and whose flange is equipped with thermal protection, a filler consisting of a set of cassettes installed on each other, and a service platform installed inside the reactor pressure vessel between the filler and guide plate.
Date Recue/Date Received 2021-12-30 This system in accordance with its design features has the following disadvantages, namely:
- at the moment of melt-through (destruction) of the reactor pressure vessel by corium, overheated melt begins to flow into the aperture formed under the impact of residual pressure in the reactor pressure vessel, distributing non-symmetrically inside the volume of the layered vessel, which is accompanied by dynamic contacts of the melt with peripheral structures leading to damage of the peripheral structures and equipment installed on the flange of the layered vessel;
- with jets of overheated melt in large volumes flowing inside the layered vessel towards the filler and as a result of repelling from the filler, a part of the overheated melt is moved in reverse direction towards the peripheral structures and layered vessel with water supply valves installed (WSV) on it, that leads to their damage and destruction;
- with flow of melt inside the layered vessel into the filler a melt level is formed, such that fall of core fragments and reactor vessel head in it leads to the formation of splashes (waves) of melt capable of damaging the peripheral equipment and WSV installed in the layered vessel;
- aerosols are formed in the process of melt outflow from the reactor pressure vessel and on interaction with the filler, and move to the top from the hot areas and settling in the cold areas on the peripheral equipment and on WSV that leads to damage of peripheral equipment and WSV installed in the layered vessel;
- after inflow of melt inside the layered vessel premature water supply inside the layered vessel is possible due to premature melt-through of WSV, as a result of which excessive high-pressure gas generation may take place that will lead to explosion and damage of the system for confining and cooling melt from the reactor core.
The system for confining and cooling melt from the core of a nuclear reactor, containing the guide plate installed below the reactor pressure vessel and resting on the cantilever truss, installed in the embedded parts in the foundation of the concrete
THE CORE OF A NUCLEAR REACTOR
Pertinent art The invention relates to the field of nuclear power engineering, and more particularly to systems, which provide for the safety of nuclear power plants (NPP), and can be used in the event of serious accidents leading to the destruction of the pressure vessel and sealed containment structure of the reactor.
The accidents with core meltdown, which may take place during multiple io failure of the core cooling system, constitute the greatest radiation hazard.
During such accidents the core melt ¨ corium ¨ by melting the core structures and reactor pressure vessel escapes outside, and the afterheat retained in it may disturb the integrity of the NPP containment ¨ the last barrier in the escape routes of radioactive products to the environment.
is To exclude this, it is required to confine the core melt (corium) escaping from the reactor pressure vessel and provide its continuous cooling up to its complete crystallization. The system for confining and cooling melt from the core of a nuclear reactor performs this function, which prevents the damage of the NPP
containment and thereby protects the public and environment against exposure effect during 20 severe accidents of the nuclear reactors.
Prior art The system for confining and cooling melt from the core [1] of a nuclear reactor, which contains a guide plate installed under the reactor pressure vessel and resting on the cantilever truss installed in the embedded parts in the foundation of the 25 concrete pit of the layered vessel, and whose flange is equipped with thermal protection, a filler consisting of a set of cassettes installed on each other, and a service platform installed inside the reactor pressure vessel between the filler and guide plate.
Date Recue/Date Received 2021-12-30 This system in accordance with its design features has the following disadvantages, namely:
- at the moment of melt-through (destruction) of the reactor pressure vessel by corium, overheated melt begins to flow into the aperture formed under the impact of residual pressure in the reactor pressure vessel, distributing non-symmetrically inside the volume of the layered vessel, which is accompanied by dynamic contacts of the melt with peripheral structures leading to damage of the peripheral structures and equipment installed on the flange of the layered vessel;
- with jets of overheated melt in large volumes flowing inside the layered vessel towards the filler and as a result of repelling from the filler, a part of the overheated melt is moved in reverse direction towards the peripheral structures and layered vessel with water supply valves installed (WSV) on it, that leads to their damage and destruction;
- with flow of melt inside the layered vessel into the filler a melt level is formed, such that fall of core fragments and reactor vessel head in it leads to the formation of splashes (waves) of melt capable of damaging the peripheral equipment and WSV installed in the layered vessel;
- aerosols are formed in the process of melt outflow from the reactor pressure vessel and on interaction with the filler, and move to the top from the hot areas and settling in the cold areas on the peripheral equipment and on WSV that leads to damage of peripheral equipment and WSV installed in the layered vessel;
- after inflow of melt inside the layered vessel premature water supply inside the layered vessel is possible due to premature melt-through of WSV, as a result of which excessive high-pressure gas generation may take place that will lead to explosion and damage of the system for confining and cooling melt from the reactor core.
The system for confining and cooling melt from the core of a nuclear reactor, containing the guide plate installed below the reactor pressure vessel and resting on the cantilever truss, installed in the embedded parts in the foundation of the concrete
2 Date Recue/Date Received 2021-12-30 cavity of the layered vessel, flange thereof is equipped with thermal protection, filler consisting of set of cassettes installed on each other, service platform installed inside the pressure vessel between the filler and guide plate is known.
This system in accordance with its design features has the following disadvantages, namely:
- at the moment of melt-through (destruction) of the reactor pressure vessel by corium, overheated melt begins to flow into the aperture formed under the impact of residual pressure in the reactor pressure vessel, distributing non-symmetrically inside the volume of the layered vessel, which is accompanied by dynamic contacts of the melt with peripheral structures leading to damage of the peripheral structures and equipment installed on the flange of the layered vessel;
- with jets of overheated melt in large volumes flowing inside the layered vessel towards the filler and as a result of repelling from the filler, a part of the overheated melt is moved in reverse direction towards the peripheral structures and layered vessel with water supply valves installed (WSV) on it, that leads to their damage and destruction;
- with flow of melt inside the layered vessel into the filler a melt level is formed, such that fall of core fragments and reactor vessel head in it leads to the formation of splashes (waves) of melt capable of damaging the peripheral equipment and WSV installed in the layered vessel;
- aerosols are formed in the process of melt outflow from the reactor pressure vessel and on interaction with the filler, and move to the top from the hot areas and settling in the cold areas on the peripheral equipment and on WSV that leads to damage of peripheral equipment and WSV installed in the layered vessel;
- after inflow of melt inside the layered vessel premature water supply inside the layered vessel is possible due to premature melt-through of WSV, as a result of which excessive high-pressure gas generation may take place that will lead to explosion and damage of the system for confining and cooling melt from the reactor core.
This system in accordance with its design features has the following disadvantages, namely:
- at the moment of melt-through (destruction) of the reactor pressure vessel by corium, overheated melt begins to flow into the aperture formed under the impact of residual pressure in the reactor pressure vessel, distributing non-symmetrically inside the volume of the layered vessel, which is accompanied by dynamic contacts of the melt with peripheral structures leading to damage of the peripheral structures and equipment installed on the flange of the layered vessel;
- with jets of overheated melt in large volumes flowing inside the layered vessel towards the filler and as a result of repelling from the filler, a part of the overheated melt is moved in reverse direction towards the peripheral structures and layered vessel with water supply valves installed (WSV) on it, that leads to their damage and destruction;
- with flow of melt inside the layered vessel into the filler a melt level is formed, such that fall of core fragments and reactor vessel head in it leads to the formation of splashes (waves) of melt capable of damaging the peripheral equipment and WSV installed in the layered vessel;
- aerosols are formed in the process of melt outflow from the reactor pressure vessel and on interaction with the filler, and move to the top from the hot areas and settling in the cold areas on the peripheral equipment and on WSV that leads to damage of peripheral equipment and WSV installed in the layered vessel;
- after inflow of melt inside the layered vessel premature water supply inside the layered vessel is possible due to premature melt-through of WSV, as a result of which excessive high-pressure gas generation may take place that will lead to explosion and damage of the system for confining and cooling melt from the reactor core.
3 Date Recue/Date Received 2021-12-30 The system for confining and cooling melt from [3] the core of a nuclear reactor containing the guide plate installed under the nuclear reactor pressure vessel, and resting on the cantilever truss, installed in the embedded parts in the foundation of the concrete pit of the layered vessel, flange thereof is equipped with thermal protection, filler, consisting of set of cassettes installed on each other, each of them contains one central and several peripheral apertures, water supply valves installed in the branch pipes located along the perimeter of the layered vessel in the area between the upper cassette and flange, service platform installed inside the layered vessel between the filler and guide plate is known.
This system in accordance with its design features has the following disadvantages, namely:
at the moment of melt-through (destruction) of the reactor pressure vessel by corium, overheated melt begins to flow into the aperture formed under the impact of residual pressure in the reactor pressure vessel, distributing non-symmetrically inside the volume of the layered vessel, which is accompanied by dynamic contacts of the melt with peripheral structures leading to damage of the peripheral structures and equipment installed on the flange of the layered vessel;
- with jets of overheated melt in large volumes flowing inside the layered vessel towards the filler and as a result of repelling from the filler, a part of the overheated melt is moved in reverse direction towards the peripheral structures and layered vessel with water supply valves installed (WSV) on it, that leads to their damage and destruction;
- with flow of melt inside the layered vessel into the filler a melt level is formed, such that fall of core fragments and reactor vessel head in it leads to the formation of splashes (waves) of melt capable of damaging the peripheral equipment and WSV installed in the layered vessel;
- aerosols are formed in the process of melt outflow from the reactor pressure vessel and on interaction with the filler, and move to the top from the hot areas and
This system in accordance with its design features has the following disadvantages, namely:
at the moment of melt-through (destruction) of the reactor pressure vessel by corium, overheated melt begins to flow into the aperture formed under the impact of residual pressure in the reactor pressure vessel, distributing non-symmetrically inside the volume of the layered vessel, which is accompanied by dynamic contacts of the melt with peripheral structures leading to damage of the peripheral structures and equipment installed on the flange of the layered vessel;
- with jets of overheated melt in large volumes flowing inside the layered vessel towards the filler and as a result of repelling from the filler, a part of the overheated melt is moved in reverse direction towards the peripheral structures and layered vessel with water supply valves installed (WSV) on it, that leads to their damage and destruction;
- with flow of melt inside the layered vessel into the filler a melt level is formed, such that fall of core fragments and reactor vessel head in it leads to the formation of splashes (waves) of melt capable of damaging the peripheral equipment and WSV installed in the layered vessel;
- aerosols are formed in the process of melt outflow from the reactor pressure vessel and on interaction with the filler, and move to the top from the hot areas and
4 Date Recue/Date Received 2021-12-30 settling in the cold areas on the peripheral equipment and on WSV that leads to damage of peripheral equipment and WSV installed in the layered vessel;
- after inflow of melt inside the layered vessel premature water supply inside the layered vessel is possible due to premature melt-through of WSV, as a result of which excessive high-pressure gas generation may take place that will lead to explosion and damage of the system for confining and cooling melt from the reactor core.
Disclosure of the invention The technical result of the claimed invention is an increase in the reliability of a system for confining and cooling melt from the core of a nuclear reactor, and an increase in the efficiency of heat removal from the melt from the core of a nuclear reactor.
The tasks to be resolved by the claimed invention are the following:
- provision of protection of peripheral structures and equipment installed on the flange of the layered vessel, against damage in the process of nonaxisymmetrical outflow of the overheated melt from the core of a reactor pressure vessel;
- provision of protection of the peripheral structures and WSV against damage following repelling from the filler wherein a part of the overheated melt is moved in the reverse direction towards the peripheral structures and WSV;
- provision of protection of peripheral structures and WSV against damage following splashes (waves) of melt on fall of core fragments and fragments of reactor pressure vessel head into the corium bath.
- providing protection of peripheral structures and WSV against damage following settlement of aerosols and their subsequent collapse together with the parts of equipment into the corium bath;
- providing protection of equipment against damage during premature water supply inside the layered vessel during premature melt-through of WSV;
- after inflow of melt inside the layered vessel premature water supply inside the layered vessel is possible due to premature melt-through of WSV, as a result of which excessive high-pressure gas generation may take place that will lead to explosion and damage of the system for confining and cooling melt from the reactor core.
Disclosure of the invention The technical result of the claimed invention is an increase in the reliability of a system for confining and cooling melt from the core of a nuclear reactor, and an increase in the efficiency of heat removal from the melt from the core of a nuclear reactor.
The tasks to be resolved by the claimed invention are the following:
- provision of protection of peripheral structures and equipment installed on the flange of the layered vessel, against damage in the process of nonaxisymmetrical outflow of the overheated melt from the core of a reactor pressure vessel;
- provision of protection of the peripheral structures and WSV against damage following repelling from the filler wherein a part of the overheated melt is moved in the reverse direction towards the peripheral structures and WSV;
- provision of protection of peripheral structures and WSV against damage following splashes (waves) of melt on fall of core fragments and fragments of reactor pressure vessel head into the corium bath.
- providing protection of peripheral structures and WSV against damage following settlement of aerosols and their subsequent collapse together with the parts of equipment into the corium bath;
- providing protection of equipment against damage during premature water supply inside the layered vessel during premature melt-through of WSV;
5 Date Recue/Date Received 2021-12-30 - providing protection (thermal shielding) of WSV, installed along the perimeter of layered vessel against thermal radiation on the part of the corium mirror.
The assigned tasks are resolved because in the system for confining and cooling melt from the core of a nuclear reactor containing the guide plate (1) installed below the vessel (2) of the nuclear reactor and resting on the cantilever truss (3) installed in the embedded parts in the foundation of the concrete pit of the layered vessel (4) designed for intake and distribution of melt, flange (5) thereof is equipped with thermal protection (6), filler (7) comprising of several cassettes (8) installed on each other, each of them contains one central and several peripheral holes (9), water supply valves (10) installed in the branch pipes (11), located along the perimeter of the layered vessel (4) in the area between the upper cassette (8) and flange (5), in accordance with the invention inside the layered vessel (4) an top thermal shield (15) is additionally installed consisting of the external (21), internal (24) shells and head (22), suspended to the flange (28) of the cantilever truss (3) through heat resistant fasteners (19) installed in the heat insulating flange (18) with contact interflange gap (29) between the heat insulating flange (18) and flange (28) of the cantilever truss and covering upper part of the thermal protection (6) of the flange (5) of the layered vessel (4), provided that the space between the external shell (21), internal shell (24) and head (22) is filled with melting concrete (26), separated into sectors by vertical ribs (20) and retained by the vertical (23), long radial (25) and short radial (27) reinforcement rods, besides the strength of the external shell (21) is above the strength of internal shell (24) and head (22), and separation elements (30) are executed in internal shell (24), bottom thermal shield (12) is installed in the upper cassette (8), consisting of the external (14), internal (31) shells and head (13), contacting with the separation elements (30) of the lower part of the top thermal shield (15), provided that in the lower part of the bottom thermal shield (12) arched elements (17) are executed, which cover the thermal protection (6) of the flange (5) of the layered vessel (4), moreover the space between the external shell (14), internal shell (31) and head (13) is filled with slag forming concrete (33), divided into sectors
The assigned tasks are resolved because in the system for confining and cooling melt from the core of a nuclear reactor containing the guide plate (1) installed below the vessel (2) of the nuclear reactor and resting on the cantilever truss (3) installed in the embedded parts in the foundation of the concrete pit of the layered vessel (4) designed for intake and distribution of melt, flange (5) thereof is equipped with thermal protection (6), filler (7) comprising of several cassettes (8) installed on each other, each of them contains one central and several peripheral holes (9), water supply valves (10) installed in the branch pipes (11), located along the perimeter of the layered vessel (4) in the area between the upper cassette (8) and flange (5), in accordance with the invention inside the layered vessel (4) an top thermal shield (15) is additionally installed consisting of the external (21), internal (24) shells and head (22), suspended to the flange (28) of the cantilever truss (3) through heat resistant fasteners (19) installed in the heat insulating flange (18) with contact interflange gap (29) between the heat insulating flange (18) and flange (28) of the cantilever truss and covering upper part of the thermal protection (6) of the flange (5) of the layered vessel (4), provided that the space between the external shell (21), internal shell (24) and head (22) is filled with melting concrete (26), separated into sectors by vertical ribs (20) and retained by the vertical (23), long radial (25) and short radial (27) reinforcement rods, besides the strength of the external shell (21) is above the strength of internal shell (24) and head (22), and separation elements (30) are executed in internal shell (24), bottom thermal shield (12) is installed in the upper cassette (8), consisting of the external (14), internal (31) shells and head (13), contacting with the separation elements (30) of the lower part of the top thermal shield (15), provided that in the lower part of the bottom thermal shield (12) arched elements (17) are executed, which cover the thermal protection (6) of the flange (5) of the layered vessel (4), moreover the space between the external shell (14), internal shell (31) and head (13) is filled with slag forming concrete (33), divided into sectors
6 Date Recue/Date Received 2021-12-30 by vertical ribs (32) and retained by vertical (34), long radial (35) and short radial (16) reinforcement rods, provided that the strength of the external load-bearing shell (14) is above the strength of the internal shell (31), head (13) and arched elements (17).
One of the essential feature of the claimed invention is the availability in the system for confining and cooling melt from the core of a nuclear reactor of the top thermal shield suspended to the cantilever truss and covering the upper part of thermal protection of the layered vessel flange with formation of slit-type gap, preventing direct impact action on the part of melt from the reactor pressure vessel in the leak-tight connection area of the layered vessel with cantilever truss.
The top thermal shield provides protection of peripheral structures and WSV against damage following repelling from the filler, wherein a part of the overheated melt outflowing from the reactor pressure vessel is moved in the reverse direction towards the peripheral structures and WSV, provides protection of the peripheral structures and WSV against damage following splashes (waves) of melt on fall of core fragments and fragments of the reactor pressure vessel into the melt bath.
One more essential feature of the claimed invention is the availability of bottom thermal shield installed in the upper cassette in the system for confining and cooling melt from the core of a nuclear reactor. The bottom thermal shield consists of external, internal shells and head. The bottom thermal shield contacts with the separation elements of the lower part of top thermal shield, in the lower part thereof arched elements are executed covering the thermal protection of the layered vessel flange. The external shell is covered with layer of slag-forming concrete, divided into sectors by vertical ribs and retained by vertical long radial and short radial reinforcement rods, and executed in such manner that its strength is above the strength of the internal shell, head and arched elements. The bottom thermal shield provides thermal shielding of the water supply valves installed along the perimeter of the layered vessel against thermal radiation on the part of corium mirror, provides protection of peripheral structures and equipment installed on the flange of the
One of the essential feature of the claimed invention is the availability in the system for confining and cooling melt from the core of a nuclear reactor of the top thermal shield suspended to the cantilever truss and covering the upper part of thermal protection of the layered vessel flange with formation of slit-type gap, preventing direct impact action on the part of melt from the reactor pressure vessel in the leak-tight connection area of the layered vessel with cantilever truss.
The top thermal shield provides protection of peripheral structures and WSV against damage following repelling from the filler, wherein a part of the overheated melt outflowing from the reactor pressure vessel is moved in the reverse direction towards the peripheral structures and WSV, provides protection of the peripheral structures and WSV against damage following splashes (waves) of melt on fall of core fragments and fragments of the reactor pressure vessel into the melt bath.
One more essential feature of the claimed invention is the availability of bottom thermal shield installed in the upper cassette in the system for confining and cooling melt from the core of a nuclear reactor. The bottom thermal shield consists of external, internal shells and head. The bottom thermal shield contacts with the separation elements of the lower part of top thermal shield, in the lower part thereof arched elements are executed covering the thermal protection of the layered vessel flange. The external shell is covered with layer of slag-forming concrete, divided into sectors by vertical ribs and retained by vertical long radial and short radial reinforcement rods, and executed in such manner that its strength is above the strength of the internal shell, head and arched elements. The bottom thermal shield provides thermal shielding of the water supply valves installed along the perimeter of the layered vessel against thermal radiation on the part of corium mirror, provides protection of peripheral structures and equipment installed on the flange of the
7 Date Recue/Date Received 2021-12-30 layered vessel against damage in the process of non-axisymmetrical outflow of overheated melt from the reactor pressure vessel, provided protection of peripheral structures and WSV against damage following the repelling from the filler, wherein the overheated melt outflowing from the reactor pressure vessel is moved in the reverse direction towards the peripheral structures and WSV, provides protection of peripheral structures and WSV against damage following splashes (waves) of corium on fall of core fragment and fragment of reactor pressure vessel head into the melt bath, provides protection of peripheral structures and WSV against damage following settlement of aerosols and their subsequent collapse together parts of equipment into the corium bath, provides equipment protection against damage on premature water supply inside the layered vessel during premature melt-through of WSV, provides protection (thermal shielding) of WSV, installed along the perimeter of layered vessel, against thermal radiation on the part of the corium mirror.
Brief description of drawings The system for confining and cooling melt from the core of a nuclear reactor executed in accordance with the claimed invention is shown in Fig. 1.
The area between the filler upper cassette and lower surface of the cantilever truss is shown in Fig. 2.
The general view of the upper heat insulation executed in accordance with claimed invention is shown in Fig. 3.
The fragment of the top thermal shield in the context executed in accordance with the claimed invention is shown in Fig. 4.
The fitting area of the top thermal shield to the cantilever truss is shown in Fig.
5.
The general view of the bottom thermal shield executed in accordance with the claimed invention is shown in Fig. 6.
The fragment of the bottom thermal shield in the context executed in accordance with the claimed invention is shown in Fig. 7.
Brief description of drawings The system for confining and cooling melt from the core of a nuclear reactor executed in accordance with the claimed invention is shown in Fig. 1.
The area between the filler upper cassette and lower surface of the cantilever truss is shown in Fig. 2.
The general view of the upper heat insulation executed in accordance with claimed invention is shown in Fig. 3.
The fragment of the top thermal shield in the context executed in accordance with the claimed invention is shown in Fig. 4.
The fitting area of the top thermal shield to the cantilever truss is shown in Fig.
5.
The general view of the bottom thermal shield executed in accordance with the claimed invention is shown in Fig. 6.
The fragment of the bottom thermal shield in the context executed in accordance with the claimed invention is shown in Fig. 7.
8 Date Recue/Date Received 2021-12-30 Embodiments of the invention As shown in Fig. 1-7, the system for confining and cooling melt from the core of a nuclear reactor comprises of the guide plate (1) installed below the reactor pressure vessel (2) and resting on the cantilever-truss (3). A layered vessel (4) is installed below the cantilever truss (3), which is installed in the foundation of the reactor pit on embedded parts. The layered vessel (4) is designed for corium intake and distribution. A flange (5) provided with thermal protection (6) is executed in the upper part of the layered vessel (4). A filler (7) is installed inside the layered vessel (4). The filler (7) consists of several cassettes (8) installed on one another, each containing one central and several peripheral holes (9). The water supply valves (10) installed in the branch pipes (11) are located in the area between the upper cassette (8) and flange (5) along the perimeter of the layered vessel (4). In addition, the top thermal shield (15) is installed inside the layered vessel (4).
The top thermal shield (15) comprises of external (21), internal (24) shells and head (22). The top thermal shield (15) is suspended to the cantilever truss flange (28) by heat-resistant fasteners (19). The heat-resistant fasteners (19) are installed in the thermal insulating flange (18) with the formation of contact inter-flange gap (29) between the thermal insulating flange (18) and cantilever truss flange (28).
The top thermal shield (15) is installed in such manner that it covers the upper part of thermal protection (6) of the flange (5) of layered vessel (4) and lower part of the cantilever truss (3). The space between the external shell (21), internal shell (24) and head (22) is filled with melting concrete (26), which is divided into sectors by the vertical ribs (20). In addition, the melting concrete is retained by vertical (23), long radial (25) and short radial (27) reinforcement rods. In this case, the strength of the external barrier (21) is above the strength of the internal barrier (24) and head (22), and separation elements (30) are executed in the internal barrier (24).
The bottom thermal shield (12) consisting of the external (14), internal (31) barriers and head (13) is installed on the upper cassette (8). The bottom thermal shield contact with the separation elements (30) of the lower part of the top thermal
The top thermal shield (15) comprises of external (21), internal (24) shells and head (22). The top thermal shield (15) is suspended to the cantilever truss flange (28) by heat-resistant fasteners (19). The heat-resistant fasteners (19) are installed in the thermal insulating flange (18) with the formation of contact inter-flange gap (29) between the thermal insulating flange (18) and cantilever truss flange (28).
The top thermal shield (15) is installed in such manner that it covers the upper part of thermal protection (6) of the flange (5) of layered vessel (4) and lower part of the cantilever truss (3). The space between the external shell (21), internal shell (24) and head (22) is filled with melting concrete (26), which is divided into sectors by the vertical ribs (20). In addition, the melting concrete is retained by vertical (23), long radial (25) and short radial (27) reinforcement rods. In this case, the strength of the external barrier (21) is above the strength of the internal barrier (24) and head (22), and separation elements (30) are executed in the internal barrier (24).
The bottom thermal shield (12) consisting of the external (14), internal (31) barriers and head (13) is installed on the upper cassette (8). The bottom thermal shield contact with the separation elements (30) of the lower part of the top thermal
9 Date Recue/Date Received 2021-12-30 shield (15). Arched elements are executed in the lower part of the bottom thermal shield (12), which on installation in the layered vessel (4) with its lower part cover the water supply valve (10) against direct impact on the part of overheated melt, and with its upper part provide unconstrained intake of overheated melt into the hole (9) of the cassettes (8).
The space between the external shell (14), internal shell (31) and head (13) has been filled with slag forming concrete (33), divided into sectors by vertical ribs (32) and retained by vertical (34), long radial (35) and short radial (16) reinforcement rods. The strength of the external shell (14) is above the strength of the internal shell (31), head (13) and arched elements (17).
The claimed system for confining and cooling core from the nuclear reactor according to the claimed invention operates as follows.
At the time of nuclear reactor pressure vessel (2) damage the melt under the action of hydrostatic and residual pressures begins to enter on the guide plate (1) surface, retained by the cantilever truss (3). The melt running down along the guide plate (1) enters the layered vessel (4) and enters into contact with the filler (7).
During sectoral non-axisymmetrical run down of the melt, the thermal protections of the cantilever truss (3), thermal protection (6) of the flange (5) of the layered vessel (4), upper (15) and lower (12) thermal protections are flashing. By disintegrating these thermal protections on the one part thermal action of melt on the protected equipment is reduced, on the other part the temperature and chemical activity of the melt itself is reduced.
Thermal protection (6) of the flange (5) of the layered vessel (4) provides protection of its upper thick-walled internal part against thermal action on the part of the corium mirror from the time of melt intake into the filler (7) and to the end of interaction of melt with the filler (7), i.e. to the start time of cooling of the clinker located on the corium surface with water. The thermal protection (6) of the flange (5) of the multi-layered vessel (4) is installed in such manner that allows provide protection of the internal surface of the multi-layered vessel (4) above the corium Date Recue/Date Received 2021-12-30 level formed in the layered vessel 94) in the interaction process with the filler (7), in particular, by that upper part of the layered vessel (4) providing normal (without heat exchange crisis in boiling mode in large quantity) heat transfer from corium to water present on the external side of the layered vessel (4).
The thermal protection (6) of the flange (5) of the layered vessel (4) in the process of interaction of the melt with the filler (7) is subject to heating and partial disintegration, by shielding heat insulation on the part of melt mirror. The geometrical and thermal and physical characteristics of thermal protection (6) of the flange (5) of the layered vessel (4) are selected in such manner that at any conditions .. shielding of the flange (5) of the layered vessel (4) is provided on the part of corium mirror thanks to which in turn the independence of protective functions from completion time of the physical and chemical interaction processes of corium with the filler (78) is provided. Thus, the availability of thermal protection (6) of the flange 95) of the layered vessel (4) allows provide perform the protective functions .. before the start of water supply to the crust located on the corium surface.
As shown in Fig. 1, 3, 4, the top thermal shield (15), suspended to the cantilever truss (3) is above the upper level of thermal protection (6) of the flange (5) of the layered vessel (4), it covers the upper part of thermal protection (6) of the flange (5) of the layered vessel (4) with its lower part providing protection against the .. impact of thermal radiation on the part of corium mirror not only of the lower part of the cantilever truss (3) but the upper part of the thermal protection 96) of the flange 95) of the multi-layered vessel 94). The geometrical characteristics such as the distance between the external surface of the top thermal shield (15) and internal surface of thermal protection (6) of the flange (5) of the layered vessel (4), and height of the covering of the specified thermal protections (15 and 6) have been selected in such manner to provide the absence of damages of the upper part of thermal protection (6) of the flange (5) of the multi-layered vessel (4) that provides its mechanical stability, consequence thereof being the protection above the water Date Recue/Date Received 2021-12-30 supply valves (10) against direct interaction on the part of overheated melt and flying objects.
As shown in Fig 3, 4 in terms of design the top thermal shield (15) consists of the external (21), internal (24) shells and head (22). As shown in Fig. 5, the top thermal shield (15) is suspended to the flange (28) of the cantilever truss (3) by heat-resistant fasteners (19). The heat-resistant fasteners (19) are installed in the thermal insulating flange (18) with the formation of contact inter-flange gap (29) between the thermal insulating flange (18) and cantilever truss flange (28). The top thermal shield (15) has been installed in such manner that it covers the upper part of thermal protection (6) of the flange (5) of the layered vessel (4) and lower part of the flange (28) of the cantilever truss. The space between the external shell (21), internal shell (24) and head (22) is filled with melting concrete (26). In addition, the melting concrete (26) is retained by vertical (23), long radial (25) and short radial(27) reinforcement rods. In this case, the strength of the external barrier (21) is above the strength of the internal barrier (24) and head (22), and separation elements (30) are executed in the internal barrier (24).
As shown in Fig. 6, 7, in terms of design the bottom thermal shield (12) consists of the external (14), internal (31) shells and head (13). As shown in Fig. 4, the bottom thermal shield (12) contacts with the separation elements (30) of the lower part of the top thermal shield (15). As shown in Fig. 6, in the lower part of the bottom thermal shield (12) arched elements (17) are executed, which when installed in the layered vessel (4) covers the thermal protection (6) of the flange (5) of the layered vessel (4). The space between the external shell (14), internal shell (31) and head (13) is filled with slag forming concrete (33), divided into sectors by vertical ribs (32) and .. retained by vertical (34), long radial (35) and short radial (16) reinforcement rods. In this case, the strength of the external shell (14) is above the strength of internal shell (31), head (13) and arched elements (17).
The bottom thermal shield (12) provides thermal shielding of the water supply valves (10) installed along the perimeter of the layered vessel (4) in the area between Date Recue/Date Received 2021-12-30 the upper cassette (8) and filler (7) and flange 95) of the layered vessel (4) against impact of the thermal insulation on the part of corium mirror.
As shown in Fig. 1, the bottom thermal shield (12) installed inside the layered vessel 94) rests on the upper cassette (8) of the filler (7) and covers the lower part of the top thermal shield (15). Such a covering is provided by coaxial installation of the bottom thermal shield (12) inside the top thermal shield (15). The covering height and process gap between the lower and top thermal shields (15 and 12) provide stable position of the top thermal shield 915) on pulse pressure boost and impact non-axisymmetrical loading.
The arched elements (17) located at the base of bottom thermal shield (12) provide opening of the full cross-section of the filler (7) holes (9) that allows redistribute air (gas) flows inside the filler (7) for quick leveling of pressure between the internal volumes of the multi-layered vessel (4) and redistribute the corium entering from the reactor pressure vessel (2).
The protection of water supply valves is made passively: bottom thermal shield (12) is gradually dissolved (melted) in the corium as long as the melt interacts with the filler (7). This interaction is determined by the initial conditions of corium intake into the filler (7): on quick or slow intake of metal and oxide components of the melt.
On quick intake of metal and oxide components of the melt into the filler (7), wherein the delay in intake of oxide components is small, maximum 30 minutes (for example, on lateral melt-through of the reactor pressure vessel (2) and subsequent partial or complete disintegration of the reactor pressure vessel (2) head, the process of physical and chemical interaction is faster, density of oxide components of the corium relative to the density of metal components takes place quicker, inversion of melt takes place at an earlier stage, and as a consequence, formation of a single liquid melt bath in which the bottom thermal shield (12) is dissolved (melted), by opening thermal radiation on the part of corium mirror to the water supply valves (10) that provides their heating and actuation for cooling water inlet.
Date Recue/Date Received 2021-12-30 On slow intake of metal and oxide components of corium into the filler (7), wherein the delay of oxide components intake exceeds 30 minutes (for example, during lateral melt-through of reactor pressure vessel (2), wherein the molten steel outflows first through the hole formed in the reactor pressure vessel (2), and then with the vessel melt-through liquid oxides outflow), the process of physical and chemical interaction takes place slower, and the reduction of density of oxide components of corium takes place slower relative to the density of metal components, and corium inversion takes places at a later stage, as a consequence formation of a single liquid melt bath, in which the bottom thermal shield(12) is dissolved (melted), opening access to the water supply valves (10) to thermal radiation on the part of the corium mirror that provides its heating and actuation for passing of cooling liquid.
The quick and slow intake of metal and oxide components of the corium into the filler (7) shall lead to considerable difference of attaining same states of corium in the multi-layered vessel (4) in time, hence the use of thermal shield, i.e.
soluble in the corium of bottom thermal shield (12) provides the actuation of water supply valves
The space between the external shell (14), internal shell (31) and head (13) has been filled with slag forming concrete (33), divided into sectors by vertical ribs (32) and retained by vertical (34), long radial (35) and short radial (16) reinforcement rods. The strength of the external shell (14) is above the strength of the internal shell (31), head (13) and arched elements (17).
The claimed system for confining and cooling core from the nuclear reactor according to the claimed invention operates as follows.
At the time of nuclear reactor pressure vessel (2) damage the melt under the action of hydrostatic and residual pressures begins to enter on the guide plate (1) surface, retained by the cantilever truss (3). The melt running down along the guide plate (1) enters the layered vessel (4) and enters into contact with the filler (7).
During sectoral non-axisymmetrical run down of the melt, the thermal protections of the cantilever truss (3), thermal protection (6) of the flange (5) of the layered vessel (4), upper (15) and lower (12) thermal protections are flashing. By disintegrating these thermal protections on the one part thermal action of melt on the protected equipment is reduced, on the other part the temperature and chemical activity of the melt itself is reduced.
Thermal protection (6) of the flange (5) of the layered vessel (4) provides protection of its upper thick-walled internal part against thermal action on the part of the corium mirror from the time of melt intake into the filler (7) and to the end of interaction of melt with the filler (7), i.e. to the start time of cooling of the clinker located on the corium surface with water. The thermal protection (6) of the flange (5) of the multi-layered vessel (4) is installed in such manner that allows provide protection of the internal surface of the multi-layered vessel (4) above the corium Date Recue/Date Received 2021-12-30 level formed in the layered vessel 94) in the interaction process with the filler (7), in particular, by that upper part of the layered vessel (4) providing normal (without heat exchange crisis in boiling mode in large quantity) heat transfer from corium to water present on the external side of the layered vessel (4).
The thermal protection (6) of the flange (5) of the layered vessel (4) in the process of interaction of the melt with the filler (7) is subject to heating and partial disintegration, by shielding heat insulation on the part of melt mirror. The geometrical and thermal and physical characteristics of thermal protection (6) of the flange (5) of the layered vessel (4) are selected in such manner that at any conditions .. shielding of the flange (5) of the layered vessel (4) is provided on the part of corium mirror thanks to which in turn the independence of protective functions from completion time of the physical and chemical interaction processes of corium with the filler (78) is provided. Thus, the availability of thermal protection (6) of the flange 95) of the layered vessel (4) allows provide perform the protective functions .. before the start of water supply to the crust located on the corium surface.
As shown in Fig. 1, 3, 4, the top thermal shield (15), suspended to the cantilever truss (3) is above the upper level of thermal protection (6) of the flange (5) of the layered vessel (4), it covers the upper part of thermal protection (6) of the flange (5) of the layered vessel (4) with its lower part providing protection against the .. impact of thermal radiation on the part of corium mirror not only of the lower part of the cantilever truss (3) but the upper part of the thermal protection 96) of the flange 95) of the multi-layered vessel 94). The geometrical characteristics such as the distance between the external surface of the top thermal shield (15) and internal surface of thermal protection (6) of the flange (5) of the layered vessel (4), and height of the covering of the specified thermal protections (15 and 6) have been selected in such manner to provide the absence of damages of the upper part of thermal protection (6) of the flange (5) of the multi-layered vessel (4) that provides its mechanical stability, consequence thereof being the protection above the water Date Recue/Date Received 2021-12-30 supply valves (10) against direct interaction on the part of overheated melt and flying objects.
As shown in Fig 3, 4 in terms of design the top thermal shield (15) consists of the external (21), internal (24) shells and head (22). As shown in Fig. 5, the top thermal shield (15) is suspended to the flange (28) of the cantilever truss (3) by heat-resistant fasteners (19). The heat-resistant fasteners (19) are installed in the thermal insulating flange (18) with the formation of contact inter-flange gap (29) between the thermal insulating flange (18) and cantilever truss flange (28). The top thermal shield (15) has been installed in such manner that it covers the upper part of thermal protection (6) of the flange (5) of the layered vessel (4) and lower part of the flange (28) of the cantilever truss. The space between the external shell (21), internal shell (24) and head (22) is filled with melting concrete (26). In addition, the melting concrete (26) is retained by vertical (23), long radial (25) and short radial(27) reinforcement rods. In this case, the strength of the external barrier (21) is above the strength of the internal barrier (24) and head (22), and separation elements (30) are executed in the internal barrier (24).
As shown in Fig. 6, 7, in terms of design the bottom thermal shield (12) consists of the external (14), internal (31) shells and head (13). As shown in Fig. 4, the bottom thermal shield (12) contacts with the separation elements (30) of the lower part of the top thermal shield (15). As shown in Fig. 6, in the lower part of the bottom thermal shield (12) arched elements (17) are executed, which when installed in the layered vessel (4) covers the thermal protection (6) of the flange (5) of the layered vessel (4). The space between the external shell (14), internal shell (31) and head (13) is filled with slag forming concrete (33), divided into sectors by vertical ribs (32) and .. retained by vertical (34), long radial (35) and short radial (16) reinforcement rods. In this case, the strength of the external shell (14) is above the strength of internal shell (31), head (13) and arched elements (17).
The bottom thermal shield (12) provides thermal shielding of the water supply valves (10) installed along the perimeter of the layered vessel (4) in the area between Date Recue/Date Received 2021-12-30 the upper cassette (8) and filler (7) and flange 95) of the layered vessel (4) against impact of the thermal insulation on the part of corium mirror.
As shown in Fig. 1, the bottom thermal shield (12) installed inside the layered vessel 94) rests on the upper cassette (8) of the filler (7) and covers the lower part of the top thermal shield (15). Such a covering is provided by coaxial installation of the bottom thermal shield (12) inside the top thermal shield (15). The covering height and process gap between the lower and top thermal shields (15 and 12) provide stable position of the top thermal shield 915) on pulse pressure boost and impact non-axisymmetrical loading.
The arched elements (17) located at the base of bottom thermal shield (12) provide opening of the full cross-section of the filler (7) holes (9) that allows redistribute air (gas) flows inside the filler (7) for quick leveling of pressure between the internal volumes of the multi-layered vessel (4) and redistribute the corium entering from the reactor pressure vessel (2).
The protection of water supply valves is made passively: bottom thermal shield (12) is gradually dissolved (melted) in the corium as long as the melt interacts with the filler (7). This interaction is determined by the initial conditions of corium intake into the filler (7): on quick or slow intake of metal and oxide components of the melt.
On quick intake of metal and oxide components of the melt into the filler (7), wherein the delay in intake of oxide components is small, maximum 30 minutes (for example, on lateral melt-through of the reactor pressure vessel (2) and subsequent partial or complete disintegration of the reactor pressure vessel (2) head, the process of physical and chemical interaction is faster, density of oxide components of the corium relative to the density of metal components takes place quicker, inversion of melt takes place at an earlier stage, and as a consequence, formation of a single liquid melt bath in which the bottom thermal shield (12) is dissolved (melted), by opening thermal radiation on the part of corium mirror to the water supply valves (10) that provides their heating and actuation for cooling water inlet.
Date Recue/Date Received 2021-12-30 On slow intake of metal and oxide components of corium into the filler (7), wherein the delay of oxide components intake exceeds 30 minutes (for example, during lateral melt-through of reactor pressure vessel (2), wherein the molten steel outflows first through the hole formed in the reactor pressure vessel (2), and then with the vessel melt-through liquid oxides outflow), the process of physical and chemical interaction takes place slower, and the reduction of density of oxide components of corium takes place slower relative to the density of metal components, and corium inversion takes places at a later stage, as a consequence formation of a single liquid melt bath, in which the bottom thermal shield(12) is dissolved (melted), opening access to the water supply valves (10) to thermal radiation on the part of the corium mirror that provides its heating and actuation for passing of cooling liquid.
The quick and slow intake of metal and oxide components of the corium into the filler (7) shall lead to considerable difference of attaining same states of corium in the multi-layered vessel (4) in time, hence the use of thermal shield, i.e.
soluble in the corium of bottom thermal shield (12) provides the actuation of water supply valves
(10) at that time when the corium independent of the intake scenarios into the filler (7) shall have same thermal and chemical and mechanical state, safe for cooling the cake formed on the melt surface with water. Geometrical and thermal and physical characteristics of the bottom thermal shield (12) are selected based on the guaranteed completion of the processes of physical and chemical interaction of corium with the filler (7) independent of the rate of this interaction.
The dual mode displacement described above of the bottom thermal shield (12) related to the processes of collapse (melting, dissolving and chemical interaction) in corium formed by the components of the corium with sacrificial materials of the filler (7) is provided by different amount of energy required for collapse of each flat layer of the bottom thermal shield (12).
Due to the presence of arched elements (17) in the lower part of the bottom thermal shield (12) of the flat layer area in the lower part is considerably less than in the upper, hence the amount of energy spent for melting (disintegrating) the lower Date Recue/Date Received 2021-12-30 part shall be lesser than for the upper part layer. In this case, the rate of lowering into the melt of the lower part of the bottom thermal shield (12) made of arched elements (17) approximately is two times above the rate of lowering its upper part.
Such a design of the bottom thermal shield (12) allows at the initial interaction stage of corium with the filler (7) and bottom thermal shield (12) to provide quick non-impact covering of the sections of internal surface of the layered vessel (4) against the impact of thermal radiation on the part of the corium mirror that allows block the direct radiation heat exchange between the corium mirror and internal surface of the layered vessel (4).
In design position the operational elements of the water supply valves (10) are closed against direct radiation heat exchange by the arched elements (17) of the bottom thermal shield (12) from the time when corium is inside the filler 97) and cassettes (8) had not lost the load-bearing capacity, to the time of formation of the melt mirror and start of shape change of the filler (7).
The arched elements (17) of the bottom thermal shield (12) protect the operating elements of water supply valves (10) against the following direct and indirect actions:
- against impact by re-radiation from neighboring sections of the internal cylindrical surface of the layered vessel (4);
- against the action by thermal radiation on the part of melt mirror band, area thereof is limited by the inner diameter of the layered vessel 94), the external diameter of bottom thermal shield (12) and net area of arched elements (17).
In this case the thermal radiation acts on the lower end surface of thermal protection (6) of the flange (5) of the layered vessel (4), and re-radiation on the operating elements of the water supply valves (10) is possible without covering the circular arches by immersing the bottom thermal shield (12) in the melt;
-against direct impact of melt jet on impact and repelling from the surfaces of thermal protections (15 and 12);
Date Recue/Date Received 2021-12-30 - against direct impact of the melt splashes on fall of the reactor equipment fragments into the melt;
- against direct impact of melt jet on sectoral melt-through of thermal protections (15 and 12) in the guide plate (1) and service platform;
- against impacts on the part of core equipment fragments and nuclear reactor pressure vessel (2).
In order that the bottom thermal shield (12) on melting in the corium lowered into the melt without lugs, complete fusion and with minimum dynamic impact on the equipment of the system for confining and cooling melt from the core of a nuclear reactor the following was executed:
- outer wall of the bottom thermal shield (12) is executed in the form of shell (14) providing the required strength and shape stability due to shadow arrangement with respect to impact of radiant heat fluxes;
- small slit-type gap between the external shell (14) of the bottom thermal shield (12) and top thermal shield (15) before the melting of arched elements (17) provides minimum impact of convective heat exchange on the part of vapor-gas medium above the surface of melt mirror, for heating the external shell (14) of the bottom thermal shield (12), and after melting of the arched elements (17) and lowering of the lower part of the bottom thermal shield (12) into the melt the influence of reverse convective heat flux directed from top to bottom, on the part of the bottom thermal shield (12) flange, for additional heating of the external shell (14) is not significant;
- vertical ribs (20) of the top thermal shield (15) have been executed with allowance inside in such manner that form vertical guides for sliding of the external shell (14) of the bottom thermal shield (12) on them. This allows the bottom thermal shield (12) in the melting process to lower into the melt along the vertical ribs (20) of the top thermal shield (15) with minimum friction resistance;
- process gap between the external shell (14) of the bottom thermal shield (12) and vertical ribs (20) of the top thermal shield (15) and provides contact of Date Recue/Date Received 2021-12-30 thermal protections (15 and 12) only along several vertical ribs (20) that is provided by the sizes of process gap a little larger than the difference between the change of internal diameters of the top thermal shield (15) and change of the external diameter of bottom thermal shield (12) on thermal expansions at temperatures close to temperature of strength loss of external shell (14) of the bottom thermal shield (12).
The process gap provides the exclusion of squeezing of the lower and top thermal shields (15 and 12) in the heating process.
-small slit-type gap between the lower part of the top thermal shield (15) and upper part of thermal protection (6) of the flange (5) of layered vessel (4) provides stability of the bottom thermal shield (12) on its melting and displacement in the melt. Indirect mounting of the moving bottom thermal shield (12) about the flange (95) of the layered vessel (4) through two thermal protections (15 and 6) installed with gaps with respect to each other excludes impact dynamic actions on the flange (5) of the layered vessel (4) on the part of the moving bottom thermal shield (12) and excludes its seizure in the upper part of thermal protection (15) following the shape change of the latter. The form of the lower part of the top thermal shield (12) is retained thanks to the impact of set, the role thereof is performed by the relatively colder upper part of thermal protection (6) of the flange (5) of the layered vessel 94).
Thus, the use of upper and bottom thermal shields of the system for confining and cooling melt from the core of a nuclear reactor installed inside the multi-layered vessel in the area of its joining with the cantilever truss allowed enhance its reliability due to provision of the largest hydraulic resistance on movement of gas-vapor mixture from the inner volume of the multi-layered vessel in the space located in the area between the layered vessel and cantilever truss and standard shielding of water supply valves installed along the perimeter of the multi-layered vessel against thermal radiation on the part of the corium mirror.
Sources of information:
Date Recue/Date Received 2021-12-30 1. RF Patent No. 2576517, IPC G21C 9/016, priority dated 16.12.2014;
2. RF Patent No. 2576516, IPC G21C 9/016, priority dated 16.12.2014;
3. RF Patent No. 2696612, IPC G21C 9/016, priority dated 26.12.2018.
Date Recue/Date Received 2021-12-30
The dual mode displacement described above of the bottom thermal shield (12) related to the processes of collapse (melting, dissolving and chemical interaction) in corium formed by the components of the corium with sacrificial materials of the filler (7) is provided by different amount of energy required for collapse of each flat layer of the bottom thermal shield (12).
Due to the presence of arched elements (17) in the lower part of the bottom thermal shield (12) of the flat layer area in the lower part is considerably less than in the upper, hence the amount of energy spent for melting (disintegrating) the lower Date Recue/Date Received 2021-12-30 part shall be lesser than for the upper part layer. In this case, the rate of lowering into the melt of the lower part of the bottom thermal shield (12) made of arched elements (17) approximately is two times above the rate of lowering its upper part.
Such a design of the bottom thermal shield (12) allows at the initial interaction stage of corium with the filler (7) and bottom thermal shield (12) to provide quick non-impact covering of the sections of internal surface of the layered vessel (4) against the impact of thermal radiation on the part of the corium mirror that allows block the direct radiation heat exchange between the corium mirror and internal surface of the layered vessel (4).
In design position the operational elements of the water supply valves (10) are closed against direct radiation heat exchange by the arched elements (17) of the bottom thermal shield (12) from the time when corium is inside the filler 97) and cassettes (8) had not lost the load-bearing capacity, to the time of formation of the melt mirror and start of shape change of the filler (7).
The arched elements (17) of the bottom thermal shield (12) protect the operating elements of water supply valves (10) against the following direct and indirect actions:
- against impact by re-radiation from neighboring sections of the internal cylindrical surface of the layered vessel (4);
- against the action by thermal radiation on the part of melt mirror band, area thereof is limited by the inner diameter of the layered vessel 94), the external diameter of bottom thermal shield (12) and net area of arched elements (17).
In this case the thermal radiation acts on the lower end surface of thermal protection (6) of the flange (5) of the layered vessel (4), and re-radiation on the operating elements of the water supply valves (10) is possible without covering the circular arches by immersing the bottom thermal shield (12) in the melt;
-against direct impact of melt jet on impact and repelling from the surfaces of thermal protections (15 and 12);
Date Recue/Date Received 2021-12-30 - against direct impact of the melt splashes on fall of the reactor equipment fragments into the melt;
- against direct impact of melt jet on sectoral melt-through of thermal protections (15 and 12) in the guide plate (1) and service platform;
- against impacts on the part of core equipment fragments and nuclear reactor pressure vessel (2).
In order that the bottom thermal shield (12) on melting in the corium lowered into the melt without lugs, complete fusion and with minimum dynamic impact on the equipment of the system for confining and cooling melt from the core of a nuclear reactor the following was executed:
- outer wall of the bottom thermal shield (12) is executed in the form of shell (14) providing the required strength and shape stability due to shadow arrangement with respect to impact of radiant heat fluxes;
- small slit-type gap between the external shell (14) of the bottom thermal shield (12) and top thermal shield (15) before the melting of arched elements (17) provides minimum impact of convective heat exchange on the part of vapor-gas medium above the surface of melt mirror, for heating the external shell (14) of the bottom thermal shield (12), and after melting of the arched elements (17) and lowering of the lower part of the bottom thermal shield (12) into the melt the influence of reverse convective heat flux directed from top to bottom, on the part of the bottom thermal shield (12) flange, for additional heating of the external shell (14) is not significant;
- vertical ribs (20) of the top thermal shield (15) have been executed with allowance inside in such manner that form vertical guides for sliding of the external shell (14) of the bottom thermal shield (12) on them. This allows the bottom thermal shield (12) in the melting process to lower into the melt along the vertical ribs (20) of the top thermal shield (15) with minimum friction resistance;
- process gap between the external shell (14) of the bottom thermal shield (12) and vertical ribs (20) of the top thermal shield (15) and provides contact of Date Recue/Date Received 2021-12-30 thermal protections (15 and 12) only along several vertical ribs (20) that is provided by the sizes of process gap a little larger than the difference between the change of internal diameters of the top thermal shield (15) and change of the external diameter of bottom thermal shield (12) on thermal expansions at temperatures close to temperature of strength loss of external shell (14) of the bottom thermal shield (12).
The process gap provides the exclusion of squeezing of the lower and top thermal shields (15 and 12) in the heating process.
-small slit-type gap between the lower part of the top thermal shield (15) and upper part of thermal protection (6) of the flange (5) of layered vessel (4) provides stability of the bottom thermal shield (12) on its melting and displacement in the melt. Indirect mounting of the moving bottom thermal shield (12) about the flange (95) of the layered vessel (4) through two thermal protections (15 and 6) installed with gaps with respect to each other excludes impact dynamic actions on the flange (5) of the layered vessel (4) on the part of the moving bottom thermal shield (12) and excludes its seizure in the upper part of thermal protection (15) following the shape change of the latter. The form of the lower part of the top thermal shield (12) is retained thanks to the impact of set, the role thereof is performed by the relatively colder upper part of thermal protection (6) of the flange (5) of the layered vessel 94).
Thus, the use of upper and bottom thermal shields of the system for confining and cooling melt from the core of a nuclear reactor installed inside the multi-layered vessel in the area of its joining with the cantilever truss allowed enhance its reliability due to provision of the largest hydraulic resistance on movement of gas-vapor mixture from the inner volume of the multi-layered vessel in the space located in the area between the layered vessel and cantilever truss and standard shielding of water supply valves installed along the perimeter of the multi-layered vessel against thermal radiation on the part of the corium mirror.
Sources of information:
Date Recue/Date Received 2021-12-30 1. RF Patent No. 2576517, IPC G21C 9/016, priority dated 16.12.2014;
2. RF Patent No. 2576516, IPC G21C 9/016, priority dated 16.12.2014;
3. RF Patent No. 2696612, IPC G21C 9/016, priority dated 26.12.2018.
Date Recue/Date Received 2021-12-30
Claims
1. The system for confining and cooling melt from the core of a nuclear reactor comprising of the guide plate (1) installed under the nuclear reactor pressure vessel (2) and resting on the cantilever truss (3), installed on the embedded parts at the base .. of the concrete pit of the layered reactor pressure vessel (4) designed for receipt and distribution of corium, flange (5) which is provided with thermal protection (6), filler (7), consisting of several cassettes installed on each other (8), each of them contains one central and several peripheral apertures (9), water supply valves (10), installed in the branch pipes (11), located along the perimeter of the multi-layered casing (4) in the area between the upper cassette (8) and flange (5), characterized in that inside the multi-layered casing (4) an top thermal shield (15) is installed in addition, comprising of the external (21), internal (24) shells and head (22), internal (24) shells and head (22), suspended to the flange (28) of the cantilever truss (3) by means of heat resistant fittings (19), installed in the heat insulating flange (18) with contact interflange gap (29) between the heat insulating flange (18) and flange (28) of the cantilever truss and covering the upper part of the thermal protection (6) of the flange (5) of the layered casing (4), provided that the space between the external shell (21), head (22) and internal shell (24) is filled with floating concrete (26), separated into sectors by the vertical ribs (20) and retained by the vertical (23), long radial (25) and .. short radial (27) reinforcement rods, and executed in such manner that its strength is higher than the strength of the internal shell (24) and the head (22), and on the internal shell (24) separating elements (30) are executed, on the upper cassette (8) the bottom thermal shield (12) is installed comprising of external (14), internal (31) shells and head (13), contacting with the distancing elements (30) of the lower part of the top thermal shield (15), in the lower part thereof arched elements (17) are executed, covering the thermal protection (6) of the flange (5) of the multi-layered casing (4), provided that the space between the external (14), internal (31) shells and head (13) is filled with slag forming concrete (33), divided into sectors by the vertical ribs (32) and retained by the vertical (34), long radial (35) and short radial (16) Date Recue/Date Received 2021-12-30 reinforcement rods, provided that the strength of the external shell (21) is above the strength of the internal shell 931), head (13) and arched elements (17).
Date Recue/Date Received 2021-12-30
Date Recue/Date Received 2021-12-30
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| RU2020111299 | 2020-03-18 | ||
| RU2020111299A RU2742583C1 (en) | 2020-03-18 | 2020-03-18 | Nuclear reactor core melt localization and cooling system |
| PCT/RU2020/000765 WO2021188007A1 (en) | 2020-03-18 | 2020-12-29 | System for confining and cooling melt from the core of a nuclear reactor |
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| Publication Number | Publication Date |
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| CA3145777A1 true CA3145777A1 (en) | 2021-09-23 |
| CA3145777C CA3145777C (en) | 2024-04-30 |
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| CA3145777A Active CA3145777C (en) | 2020-03-18 | 2020-12-29 | System for confining and cooling melt from the core of a nuclear reactor |
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| DE2741795A1 (en) * | 1977-09-16 | 1979-03-29 | Interatom | CORE REACTOR COLLECTION PAN WITH THERMAL INSULATION |
| US4442065A (en) * | 1980-12-01 | 1984-04-10 | R & D Associates | Retrofittable nuclear reactor core catcher |
| RU2165107C2 (en) * | 1999-06-02 | 2001-04-10 | Санкт-Петербургский научно-исследовательский и проектно-конструкторский институт АТОМЭНЕРГОПРОЕКТ | Protective system of protective shell of water-cooled reactor plant |
| RU2165108C2 (en) * | 1999-06-15 | 2001-04-10 | Санкт-Петербургский научно-исследовательский и проектно-конструкторский институт АТОМЭНЕРГОПРОЕКТ | Protective system of protective shell of water-cooled reactor plant |
| RU100327U1 (en) * | 2010-06-17 | 2010-12-10 | Открытое акционерное общество "Санкт-Петербургский научно-исследовательский и проектно-конструкторский институт "АТОМЭНЕРГОПРОЕКТ" (ОАО "СПбАЭП") | MELT LOCALIZATION DEVICE |
| CN102097137B (en) * | 2010-10-28 | 2014-05-07 | 中国核工业二三建设有限公司 | Method for installing reactor core catcher of nuclear power station |
| EP2715734B1 (en) * | 2011-06-03 | 2017-03-08 | Claudio Filippone | Passive decay heat removal and related methods |
| CN103377720B (en) * | 2012-04-27 | 2016-01-27 | 上海核工程研究设计院 | Out-pile fused mass arresting device after a kind of nuclear power plant accident |
| CN103474107A (en) * | 2012-06-08 | 2013-12-25 | 中国核动力研究设计院 | Comprehensive protection device of nuclear reactor container |
| RU2576516C1 (en) * | 2014-12-16 | 2016-03-10 | Акционерное Общество "Атомэнергопроект" | System of localisation and cooling of melt of active zone of pressurised water reactor |
| MY196713A (en) * | 2014-12-16 | 2023-05-02 | Joint Stock Company Atomenergoproekt | Water-cooled water-moderated nuclear reactor core melt cooling and confinement system |
| RU2576517C1 (en) * | 2014-12-16 | 2016-03-10 | Акционерное Общество "Атомэнергопроект" | System for localisation and cooling of water-water nuclear reactor core region melt |
| RU2696004C1 (en) * | 2018-08-29 | 2019-07-30 | Акционерное Общество "Атомэнергопроект" | System for localization and cooling of molten core of nuclear reactor of water-cooled type |
| RU2700925C1 (en) * | 2018-09-25 | 2019-09-24 | Акционерное Общество "Атомэнергопроект" | Nuclear reactor core melt localization device |
| RU2696012C1 (en) * | 2018-11-08 | 2019-07-30 | Федеральное государственное унитарное предприятие "Научно-исследовательский технологический институт имени А.П. Александрова" | Device for localization of corium of nuclear reactor of pressurized water type |
| RU2696612C1 (en) * | 2018-12-26 | 2019-08-05 | Акционерное Общество "Атомэнергопроект" | Melt localization device |
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- 2020-03-18 RU RU2020111299A patent/RU2742583C1/en active
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| CA3145777C (en) | 2024-04-30 |
| ZA202110609B (en) | 2022-10-26 |
| CN114424296A (en) | 2022-04-29 |
| JOP20210343A1 (en) | 2023-01-30 |
| WO2021188007A1 (en) | 2021-09-23 |
| KR102626473B1 (en) | 2024-01-17 |
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